ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
April 2025
Latest News
State legislation: Delaware delving into nuclear energy possibilities
A bill that would create a nuclear energy task force in Delaware has passed the state Senate and is now being considered in the House of Representatives.
Noboru Kobayashi, Ryota Hirano, Youichi Enokida, Ichiro Yamamoto
Fusion Science and Technology | Volume 44 | Number 2 | September 2003 | Pages 415-419
Technical Paper | Fusion Energy - Tritium and Safety and Environment | doi.org/10.13182/FST03-A370
Articles are hosted by Taylor and Francis Online.
The pressure dependence of separation factors of the columns for H2-HT mixture was measured for practical design of "cryogenic-wall" thermal diffusion columns for tritium handling system. Experiments were performed with 1,020 mm-height column with a 4.8 mm-outer-radius tube heated by hot-water and a 11.5 mm-inner-radius tube cooled by liquid nitrogen. The maximum total separation factor was 12.7 at 80 kPa for H2-HT separation. By using another column with 9.53 mm-outer-radius tube heated by hot-water and a 14.2 mm-inner-radius tube, the separation factor was 64.4 at 144 kPa, and the separation will be larger at higher pressure.Comparison of numerical calculations of axial and radial two-dimensional flow and concentration distribution with experimental data revealed that our code could predict the pressure dependence of separation factor of the columns well.